ML20093M429

Proposed Tech Specs,Extending 18-month Surveillances to 960331

ML20093M429
Person / Time
Site:	Calvert Cliffs
Issue date:	10/20/1995
From:	BALTIMORE GAS & ELECTRIC CO.
To:
Shared Package
ML20093M419	List: ML20093M414 ML20093M429
References
NUDOCS 9510260282
Download: ML20093M429 (14)

Text

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3/4.3 INSTRUMENTATION 3/4.3.1 REACTOR PROTECTIVE INSTRUMENTATION LIMITING CONDITION FOR OPERATION

^i 3.3.1.1 As a minimum, the reactor protective instrumentation channels and bypasses of Table 3.3-1 shall be OPERABLE.

l APPLICABILITY: As shown in Table 3.3-1.

ACTION: As shown in Table 3.3-1.

SURVEILLANCE REQUIREMENTS 4.3.1.1.1 Each reactor protective instrumentation channel shall be demonstrated OPERABLE by the performance of the CHANNEL CNECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations during the MODES and at the frequencies shown in Table 4.3-1.

4.3.1.1.2 The logic for the bypasses shall be demonstrated CPERABLE prior 1

to each reactor STARTUP unless performed during the preceding 92 days. The r'q total bypass function shall be demonstrated OPERABLE at least once per g.F/

18 monthT3during CHANNEL CALIBRATION testing of each channel 'affected by bypass operation.

The REACTOR TRIP SYSTEM RESPONSE TIME of each reactor trip 4.3.1.1.) hall be demonstrated to be within its limit at least once per l

function s 18 months.

Each test shall include at least one channel per function such that all channels are tested at least once every N times 18 months where N L

is the total number of redundant channels in a specific reactor trip function as shown in the " Total No. of Channels" column of Table 3.3-1.

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W F., CyJ, II, W 5+ cam Ge%%-l sPax % B p.es swdlwe skalike J4 Ad39t%.

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Neutron detectors are exempt from response time testing.

l' CALVERT CLIFFS - UNIT 1 3/4 3-1 Amendment No. 184 9510260282 951020 PDR ADOCK 05000317 l

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g TABLE 4.3-1 G

g g

REACTOR PROTECTIVE INSTRUNENTATION SURVEILLANCE REOUIREMENTS

-w w

M C

GAMEL MODES IN NNICR q'^

CHANNEL CHAMEL FUNCTIONAL SURVEILLANCE FUNCTIONAL UNIT

___ CHECK CALIBRATION TEST REQUIRED E

h I.

Manual Reactor Trip NA NA S/U )

NA U

~

4

2. ~ Power Level - High d.

a.

Nuclear Power S

D ),M ) QUI U

U Q

1, 2 l

b.

AT Power S

D)

U q

1

[

0 3.

Reactor Coolant Flow - Low S.

R t

Qi 1, 2 l

t R

4.

Pressurizer Pressure - High S

R 0 s

Q 1, 2 ~

l w

5.

Containment Pressure - High S

R J

Q 1, 2 l

0f Q

1, 2 l

6.

Steam Generator Pressure - Low S

R R8 [

Q 1, 2 7.

Steam Generator Water Level -

S Low l

.a 8.

Axial Flux ~0ffset S

R Q

1

}

9.

a.

Themal Margin / Low Pressure S R-Q 1, 2 l

l 4

17.- Steam Generator Pressure S-R Q

1, 2

' l t

g Difference - High l

3

10. Loss of Load NA NA S/U )

NA U

• o e

w O

e t'

I r

[

e k

- _ - - -. =

~

pg$.,.f r ;.

l 3/4.3 INSTRUMENTATI0s TABLE 4.3-1 (Continupp)_..

TABLE NOTATION i

With reactor trip breakers in the closed position and the CEA drive j

system capable of CEA withdrawal.

(1)

If not perfomed in previous 7 days.

j (2)

Heat balance only, above 15% of RATED THERMAL POWER; adjustNui: lear Power Calibrate" potentiometers to make the nuclear power signals j

agree with calorimetric calculation if absolute difference is > 1.5%.-

During PHYSICS TESTS, these daily calibrations of nuclear power and

}

AT power.may be suspended provided these calibrations are performed upon reaching each major test power plateau and prior to proceeding 3

l to the next major test power plateau.

I3)

Above'15% of' RATED THERMAL POWER, recalibrate the excore detectors

{

which monitor the AXIAL SHAPE INDEX by using the incore detectors or restrict THERMAL POWER during subsequent operations to 5 90% of the i

maximum allowed THERMAL POWER level with the existing Reactor Coolant j

Pump combination.

(4)

Above 15% of R5TED THERMAL POWER, adjust "AT Pwr Calibrate" potentiometers to null " Nuclear Pwr - AT Pwr." During PHYSICS TESTS, these daily calibrations of nuclear power and AT power may be j

suspended provided these calibrations are perfonned upon reaching t

j each major test power plateau and prior to proceeding to the next I

major test power plateau.

j (5)

Neutron detectors may be excluded from CHANNEL CALIBRATION.

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4)

For Cy.l. i2, w son,Le sWI k b 17 mmk 3g im i

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l CALVERT CLIFFS - UNIT 1 3/4 3-8 Amendment No.184 l

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3/4.3 INSTRUMENTATION 3/4.3.2 ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENT i

~n,~.

LIMITING CONDITION FOR OPERATION i

e j

-3.3.2.1 The Engineered Safety Feature Actuation System (ESFAS) instrumentation channels and bypasses shown in Table 3.3-3 shall be OPERABLE with their trip setpoints set consistent with the values shown in the Trip SetpoirJt column of Table 3.3-4.

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j APPLICABILITY: As shown in Table 3.3-3.

E ACTION:

i a.

With an ESFAS Instrumentation channel trip setpoint less conservative than the value shown in the Allowable Yalues column of Table 3.3-4. declare the channel inoperable and apply the applicable ACTION requirement of Table 3.3-3 until the channel is restored to OPERABLE status with the tri consistent with the Trip Setpoint value.p setpoint ad. justed I

i b.

With an ESFAS instrumentation channel inoperable, take the ACTION j.

shown in Table 3.3-3.

i SURVEILLANCE REeJIREMENTS I.

4.3.2.1.1 Each ESFAS instrumentation channel shall be demonstrated OPERABLE by the perfonnance-of the CHANNEL CHECK, CNANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations during the MODES and at the frequencies shown in Table 4.3-2.

The logic for th' bypasses shall be demonstrated OPERABLE during 4.3.2.1.2 e

the. at power CHANNEL FUNCTIONAL TEST of channels affected by bypass The total bypass function shall be demonstrated OPERABLE at operation.

i least once per 18 monthi&lbrin affected by bypass operation. g CHANNEL CALIBRATION testing of each channel 4.3.2.1.3 The ENGINEERED SAFETY FEATURES RESPONSE TIME of each ESFA functio all be demonstrated to be within the limit at.least once pe.r 18 mont Each test shall include at least one channel per. function sisch that all channels are tested at least once every N times 18 months where N is the total number of redundant channels'in a specific ESFAS function as t

shown in the " Total No. of Channels

• Column of Table 3.3-3.

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CALVERT CLIFFS - UNIT 1 3/4 3-9 Amendment No. 184

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G TABLE 4.3-2 w

g ENGINEERED _ SAFETY FEATURE ACTUATION SYSTEM INSTRUNENTAT D

e

?,

u m

q" CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE N

GANNEL NODES IN WRIG E

FUNCTIONAL UNIT i

_ CHECK CALIBRATION TEST REQUIRED E-e 5

1.

SAFETY INJECTION (SIAS) i a.

Manual (Trip buttons)

NA NA E

b.

Containment Pressure - High S

NA c.

Pressurizer Pressure'- Low R

Q

1. 2. 3 S

R' d.

Automatic Actuation Logic NA NA M)g101

1. 2, 3 U

2.

CONTAINMENT SPRAY (CSAS)

1. 2. 3 s"

a.

Martual '(Trip buttons)

NA NA R

Y b.

Containment Pressure - High S

R NA g

c.

Automatic Actuattori Logic NA NA MD$(4

1. 2. 3 l

3.

CONTAllWENT IS0tATION (CIS)'

1. 2, 3

.e Manual CIS.(Trip buttons) a.

NA b.

Containment Pressure - Nigh NA

c. Automatic Actuation Logic R

NA S

M j(4)

-1. 2. 3

]

's NA NA U

F

1. 2. 3

=

t E

0 e

e 4

.h.'

g TABLE 4.3-2(Continued) r-h g

a

- EMINEERED SAFETY FEATURE' ACTUATION SYSTEM INSTRUNENTATION SURVEILULNCE EE--at, sina e,

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C M

l

'i GAMEL MODES IN W ICR R

CHAMEL GAMEL FUNCTIONAL SURVEILLANCE FWCTIONAL UNIT CNECK CALIBRATION E

REWIRED i5 4.

MAIN STEM LINE ISOLATION (SGIS) d a.

ManualSGIS(MSIVHandSwitches NA NA and Feed Head Isolation Hand NA Switches) b.

Steam Generator Pressure - Low S

MgM 1, 2, 3 l

c.

Automatic Actuation Logic NA NA I

1, 2. 3 R

5.

CONTAIIGENT SUW RECIRCULATION (RAS)

Y a.

ManualRAS(TripButto's)

NA NA a

n g

b.

Refueling Water Tank - Low NA R

gg Mg3 1,.2,3 l

l c.

Automatic Actuation Logic NA NA

1. 2. 3 6.

CONTAIIWERT PURGE VALVES ISOLATION a.

Manual (

Valve Control NA NA R

NA

,i t

Switches l

b.. Conthinnent Radiation - liigh Area S

R Q

6"

]

i

(

Monitor tn

?

t.at

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O

,---w

,w

-+. __- - -, - _-_ _., _ _ _ _

_. -.. ~

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.h TABLE 4.3-2 (Continued)

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.EMINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENT A

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M.

GAREL plo0ES III WICR fFUNCTIONALWIT GAMEL GAMEL FUKTIONAL SUNTEILUDICE CHECK CALIBRATIUM E

REQUIRED E

e 5

7.

LOSS OF POWER

a. ~4.16 kv Emergency Bus Undervoltage g3,

(Loss of Voltage NA g

4.16 kV Emergency) Bus Undervoltage q

I, 2, 3 l

b.

NA (DegradedVoltage)

Q 1, 2. 3

{

8.

CYCS ISOLATION R

I West Penetration Room / Letdown Y

Heat Exchanger Room Pressure - High NA R

Q

1. 2 3. 4 l

Cl

\\

9.

AUXILIARY FEEDWATER n

Manual (Trip Buttons) a.

NA b.

Steam Generator Level - Low NA j3 R

I RA S

Steam Generator AP - High RU Q

c.

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d... Automatic Actuation Logic R

1. 2. 3 S

a NA NA

)

1. 2. 3

1. 2. 3 L

if N

tab

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l 3/4.3 INSTRUNENTATION TABL5 4.3-2 (Continued)

%,-y TABLE NOTATION

/

containment isolation of non-essential by SIAS (functional units 1.a and 1.c). penetrations is also initiated

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Must be OPERABLE only in N0DE 6 when the valves are required OPERABLE and they are open.

(1)

The logic circuits shall be tested manually at least once per 31 days.

(2)

SIAS logic circuits A-10 and B-10 shall be tested monthly with the l

exception of the Safety Injection Tank isolation valves. The SIAS logic circuits for these valves are exempted from testing during operation; however these logic circuits shall be tested at least once per 18 month uring shutdown.

(3)

SIAS logic circuits A-5, and B-5 are exempted from testing during operation; however these lo ic circuits shall be tested at least once per 18 month uring sh tdown.

(4)

CIS logic circuits A-5 and B-5 are exempted from testing during operation; howeve these logic circuits shall be tested at least once per 18 month uring shutdown.

(5)

SGIS logic circuits

-1 and 8-1 are exempted from testing during operation;.howeven these lo ic circuits shall be tested at least once per 18 monthtuuring sh tdown.

(6)

CSAS logic circuits A.-3 and B-3 are exempted from testing durtrig operation; howevermthese logic circuits shall be tested at least once er 18 monthdtiduring shutdown.

D)

For c l<. (2) % sww,'#..,g cLllk de p ofank 31,19u, e

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1. *e C de12) & surveillaare shallke d4ly dank 31 l'lif,,

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i CALVERT CLIFFS - UNIT 1 3/4 3-22 Amendment No. 193 i

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TABLE 4.3-3_

r-R RADIATION MONITORING INSTRtMENTATION SURVEILLANCE REQUIREMENTS m-U P4 CHANNEL MODES IN INIIG E

3 CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE N" -

plSTROMENT.

CHECK CALIBRATION TEST e

1.

AREA MONITORS REQUIRED E

i i5 a.

Containment d-o 1.

Purge & Exhaust Isolation S

R M

6 a

b.

Containment Area High Range S

M 2

PROCESS MONITORS 1, 2, 3, & 4 s"

a.

Containment w

,g 1.

Gaseous Activity a) RCS Leakage Detection S

R M

1, 2, 3, & 4 g

11. Particulate Activity

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a) RCS Leakage Detection S

R H

1, 2, 3, & 4 k

b. Iloble Gas Effluent Monitors g

g 1.

Main Vent Wide Range S

R M

1, 2, 3, & 4

'11. Main Steam Header S

R M

1, 2, 3, & 4 b

4

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. INSTRUNENTATION.

3/4.3 1

1 TABLE 4.3-6 I

REMOTE SHUTDOWN N0NITORING INSTRUNENTATI6Nr$URVEILLAJCE REO 1

CHANNEL CHANNEL' INSTRUNENT g[K CALIBRATION 1.

Wide Range. Neutron Flux N

NA 3

t 2.

Reactor Trip Breaker Indication N

NA 3.

Reactor Coolant Cold Leg Temperature N

R j

-l 4.

Pressurizer Pressure H

R i

I 5.

Pressurizer Level H

i

• q r

6.

Steam Generator Level (Wide Range)

H 5

4 7.

Steam Generator Pressure H

R i

1 1

=

i

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I k

CALVERT CLIFFS - UNIT 1 3/43-32 Amendment No. 199 l

=

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b.

g TABLE 4.3-10

<g POST-ACCIDENT MONITORING INSTRUNENTATION S R VEILLANC k

n w

E 3

nSrRest GAMEL GAMEL E

cNEcx CAtrimTra g

i 1.

Containment Pressure M

2.

Wide Range Logarithmic Neutron Flux Monitor R

g

[

3.

Reactor Coolant Outlet Temperature

~

m g-

[

M M

4.

Pressurizer Pressure E

5.

Pressurizer Level M

/

6.

Steam Generator Pressure.

M R

1 R

7.

M V'

Steam Generator Level (Wide Range)

=

M R, X w

8.

Auxiliary Feedwater Flow Rate M

9.

RCS Subcooled Margin Monitor Rg

-M 4

M Wj

10. PORV/ Safety Valve Acoustic Mor;itor R

Rf."a <)

11. PORY Solenoid Power Indication NA

12. Feedwater Flow m

g ', J M

13.ContainmentWaterLevel(WideRange) gpK'

14. React' r Yessel Water level M

hM l

o k

15. Core Exit Thermocouple System M

m M

R*

o The performance of a cNANNEL CALIBRATION operation exempts the Core l8 includes all electronic components.

The Core Exit Thermocouple shall be~ calibrated prior to insta11atico in the: reactor core.

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.g O eIC U % serverllence chall k d.e y

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i 3/4.4 REACTOR C00UUfT sdmi

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SURVEILLANCE REQllIRD(ENTS 4.4.3.1 E.ach PORY shall be denonstrated OPDt&BLE:

At least on a.

TEST, in acc.ce per 31 d b performance of a CHANNEL filNCTIONAL ordance wft T 1e 4.3-1 Item 4.

' b.

At least once per 18 monthhy performance of a CHANNEL CALIBRATION.

4.4.3.2' Each block valve shall be demonstrated OPERABLE at least once per t

92 days by operating the valve through one complete cycle of full travel i

unless the block valve is closed to meet the requirements of Action a, b.-

or c in Specification 3.4.3.

I J

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l For C cle t2 %somillwe skllLe dw GMmul, tqu, y

i CALVERT CLIFFS - UNIT 1 3/4 4-8 Amendment No.188 i

%.yl.

o 3/4.4 REACTOR COOLANT SYSTEM SURVEILLANCE REQUIRENENTS 4.4.6.1 The Leakage Detection Systems shall.yp demonstrated OPERABLE by:

Containment Atmosphere Gaseous and Particulate Monitoring a.

Systems-performance of CHANNEL CNECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST at the frequencies spectffed in Table 4.3-3, and b.

Containment Sump Level Alarm System-per ance of CNANNEL CALIBRATION at least once per 18 months i

a I

-l g.

M For O.f,12,%,y%;jLce shell k d e h MmL si, req 6.

p CALVERT CLIFFS - UNIT 1 3/4 4-18 Amendment No. 188 l

2:)g e

3/4.4 REACTOR COOLANT SYSTEN LIMITING CONDITION FOR OPERA 0N (Continued).

2.

Verify the excessive flow conditjon above the maximum allowable pressure.did not raise pressure

.for the given RCS l

temperature on Figure 3.4.9-1 or Figure 3.4.9-2.

i 3.

If a pressure limit was exceeded, take action in accordance j

with Specification 3.4.9.1.

h.

The provisions of Specification 3.0.4 are not applicable.

l l

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SURVEILLANCE REQUIREMENTS I

i 4.4.9.3.1 Each PORY shall be demonstrated OPERABLE by:

e Perfohnance of a CHANNEL FUNCTIONAL TEST on the PORV actuation a.

channel, but excluding valve operation, within 31 days prior to 1

entering a condition in which the PORY is required OPERABLE and j

at least once per 31 days thereafter when the PORV is required OPERABLE.

b.

Perfonnance of a CHANNEL CALIBRATIO the PORV actuation channel at'least once per 18 month i

Verifying the PORY block valve is open at least once per 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> l

c.

when the PORY is being used for overpressure protection.

i d.

Testing in accordance with the inservice test requirements

)

pursuant to Specification 4.0.5.

i 4.4.9.3.l! The RCS vent (s) shall be verified to be open at'least once j

12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> when the vent (s) is being used for overpressure protection. per 4.4.9.3.3 All high pressure safety injection pumps, except the above OPERABLE pump, shall be demonstrated inoperable at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 1

by verifying that the motor circuit breakers have been removed from their j

electrical power supply circuits or by verifying their discharge valves are locked shut.

j The automatic opening feature of the high pressure safety i

injection loo) MOVs shall be verified disabled at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

i The above OPELABLE pump shall be verified to have its handswitch in pull-to-lock at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

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.t Except when the vent intheopenposition,pathwayislocked, sealed,iirotherwisesecured 1

then verify these vent pathways open at least once per 31 days.

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1. or de il t sum 76.4 s ell he

&c.h3fl (

CAL ER L

ndment No.188 1

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